Assessment of RELAP5/MOD3.2 Against a Main Steam Isolation Valve Closure at TRILLO I Nuclear Power Plant (NUREG/IA-0172)
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Date Published: February 2000
A. de Lucas, R. L. Perezagua
Empresarios Agrupados, AIE
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Code Application and Maintenance Program (CAMP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
This report includes an assessment of RELAP5/MOD3.2 against a main steam line isolation at 99% power in Trillo I NPP (PWR, KWU-Siemens, 1040 MWe).
The results used are those obtained during test D-100-306 (Ref. 3), performed August 19, 1988 at Trillo I NPP.
The three plant cooling loops are simulated to take into account:
i. A single loop containing a valve in which the disturbance occurs
ii. The remaining two loops are simulated using two separate model loops
The Trillo I model used comprises 273 control volumes, 297 junctions, 101 heat structures and 252 control variables.
From this study it can be concluded that the post-test calculation shows a reasonable agreement with the actual plant data.